南方能源建设2024，Vol.11Issue(3)：75-80,6.DOI:10.16516/j.ceec.2024.3.08
聚变堆包层模块第一壁不同冷却剂传热性能研究
Research on Heat Transfer Performance of Different Coolants for the First Wall of the Test Blanket Module of Nuclear Fusion Reactor
摘要
Abstract
[Introduction]As a clean and efficient energy source,nuclear fusion promises to achieve global sustainable development in the future.For the first wall of Chinese helium-cooled solid breeder test blanket module,the temperature fields of helium,argon and nitrogen as coolants were calculated based on the design scheme of four coolant channels proposed by the Nuclear Thermal Security and Standardization Research Team.[Method]To calculate the heat transfer of different coolants in the first wall of the cladding module of fusion reactor,the B.S.Putukhov formula is used to calculate the heat transfer.[Result]Research indicates that the temperature field variations in the Be panel and RAFM steel are similar for helium,argon,and nitrogen as coolants.The maximum temperatures in the temperature fields are below the allowable temperature,meeting the safety requirements for temperatures.Nitrogen as a coolant offers the largest safety margin,followed by argon,with helium presenting a relatively smaller safety margin.[Conclusion]This study provides more optimization options for selecting the coolant for the first wall of the test blanket module of nuclear fusion reactor,thereby enhancing the safety margin of the first wall of the test blanket module of nuclear fusion reactor.关键词
核聚变/第一壁/氦气/氩气/氮气/冷却剂Key words
nuclear fusion/the first wall/helium/argon/nitrogen/coolant分类
核科学引用本文复制引用
张豪磊,周涛,薛春辉,刘鹏..聚变堆包层模块第一壁不同冷却剂传热性能研究[J].南方能源建设,2024,11(3):75-80,6.基金项目
江苏省双创人才经费"多介质颗粒物流动换热特性研究"(110300297) （110300297）
科技部重点研发计划"固有安全模块化金属弥散热管反应堆设计技术"(2020YFB1901700) （2020YFB1901700）
中核科技工业核动力技术创新中心项目"基于相场-流场耦合的相分离组织演变模拟技术"(6903003092) （6903003092）
